Field of the Invention
[0001] The present invention relates to a method for the removal of iodine and/or iodine
compounds from mixture gases.
Prior Art
[0002] Many methods have been proposed for the removal of iodine species contained in dissolver
off gases (hereafter referred to as "DOG") from spent nuclear fuel reprocessing plants.
These include wet methods such as the alkaline scrubbing process, Mercurex process,
and Iodox process, and the dry methods which use various kinds of solid adsorbents.
[0003] In the alkaline scrubbing process, a solution of 1 - 2 mol/l caustic soda is used
to absorb iodine from the DOG. The scrub liquor produced contains iodine compounds
such as NaI, NaOI, and NaIO₃. The disadvantage of this method is that a great deal
of sludge is produced due to reaction of caustic soda with CO₂ and nitrogen oxides
(hereafter referred to as NOx) in the DOG, in addition to the sediment of iodine compounds
produced, so that the amount of radioactive waste to be treated remarkably increases
as well as the expense of such disposal. (Literature: (1) Holladay, D.W., 1979, A
literature survey: methods of the removal of iodine species from off-gases and liquid
waste streams of nuclear power and nuclear fuel reprocessing plants, with emphasis
on solid sorbents. ORNL/TM- 6350; (2) International Atomic Energy Agency, 1980, Radioiodine
removal in nuclear facilities; Technical reports series No. 201, IAEA, Vienna; (3)
Benedict, M.,T.H. Pigford and H.W. Levi, 1981, Nuclear Chemical Engineering, McGraw-Hill
N.Y.).
[0004] The Mercurex process uses a nitric acid solution of mercuric nitrate (1-14 mol/l)
as a scrubbing solution into which iodine compounds are absorbed and converted to
HgI₂ or Hg(IO₃) to be thereafter removed. Due to the use of mercury in this process,
careful countermeasures are required to eliminate mercury pollution. (Refer to the
above literature (1), (2) and (3).) In the disclosed Mercurex process, the solution
of mercuric nitrate loaded with iodine and mercury, and then iodine, is fixed as copper
iodide and the mercury is recycled for reuse. The design of this process is thus complicated.
(Literature: (4) Collad, G.E.R.et al.,1978, Iodine trapping and conditioning in the
Mercurex system, 16th DOE Nuclear Air Cleaning Conference, p 552)
[0005] The Iodox process uses a highly concentrated nitric acid of 20 - 22m mol/l as a liquid
absorbent to precipitate and recover iodine compounds as HI₃O₈. The corrosion of the
equipment materials of construction by the concentrated nitric acid used is a serious
disadvantage of this process. (Refer to the above literature references (1), (2) and
(3).)
[0006] Most of the dry methods utilizing solid adsorbents for the removal of iodine are
based on the reactions of silver or a silver salt with iodine. For example, AC6120
is a sorbent consisting of amorphous silicic acid base material impregnated with silver
nitrate, which is capable of efficiently absorbing and removing iodine even in the
presence of NOx. (Refer to the literature reference (5): Japanese Patent SHO. 53-22077.)
It is necessary, however, to heat DOG to approximately 150°C to assure a rapid reaction
of silver nitrate with iodine and iodine compounds. (Refer to the literature references
(2) and (3)).
[0007] The Hanford Plant in the United States has achieved acceptable results in iodine
removal using a solid adsorbent consisting of unglazed saddles impregnated with silver
nitrate. Heating of the DOG is also necessary for the use of this adsorbent, however,
and it has been reported that the reaction of silver and iodine will not take place
at a temperature lower than 110°C. (Literature references: (3) and (6) "Nuclear Chemical
Engineering" by Hiroshi Yamamoto, 1976, published by Nikkan Kogyo Shimbun).
[0008] Various types of silver-exchanged zeolites have been reported to be useful for the
removal of iodine in the DOG. These adsorbents also requires an elevation of the temperature
of the DOG to 100°C or higher as in the case of the above systems. (Literature references:
(2) and (7) Thomas, T.R., B.A. Stapeles and L.P. Murphy, 1978, The development of
AgZ for bulk ¹²⁹I storage. Proc. 15th DOE Nuclear Air Cleaning Conference, p 394).
[0009] The common disadvantage of the foregoing systems using such solid adsorbents is that,
in the storage and final disposal of the spent adsorbents loaded with radioactive
iodine, the extra volumes of the carriers are definitely disadvantageous in that the
carriers having such surplus volume must also be treated as radioactive wastes.
Objects of the Invention
[0010] An object of the present invention is to provide a system which does not possess
the disadvantages of the wet and dry processes described above, which can be simple
in structure, which does not produce extra waste other than iodine compounds, which
does not require preheating of the DOG, which does not use corrosive or hazardous
chemicals such as nitric acid and mercury, and which is free from the effects of NOx
and water vapor present in the DOG. Other objects of the invention will become apparent
hereinafter, and still others will be obvious to one skilled in the art.
Brief Description of the Drawings
[0011]
FIGS. 1 to 4 are explanatory diagrams illustrating the effects of the method of the
present invention.
Description of the Invention
[0012] The objects of the present invention can be achieved by contacting mixture gases
or vapors containing iodine and/or iodine compounds, such as methl iodide with a solution
containing silver ion and by removing iodine species contained in the said gases or
vapors as a sediment or precipitate of insoluble iodides. The present invention makes
use of wet contact between mixture gases or vapors containing iodine and/or iodine
compounds with a solution containing silver ion, and belongs to the category of wet
processes rather than dry process in which silver salt is impregnated into or onto
solid substrates.
[0013] To prepare the solution containing silver ion, various kinds of silver salts such
as silsver nitrate, silver sulfate, and silver carbonate, can be used. The concentration
of silver ion can range between 0.0001 and 5 mol/l, preferably between 0.001 and 1
mol/l. The solutions may contain mineral acids such as nitric acid. As equipment for
gas-liquid contact of the solution containing silver ion and a gas to be processed,
one can use almost any type of equipment including conventional equipment such as
a bubble tower, spray tower, plate column, wetted wall column, or the like, as well
as newer types of gas-liquid contact equipment.
[0014] Mixture gases or vapors containing iodine and/or iodine compounds to be processed
by the system in accordance with the present invention may contain, for example, about
2000 ppm of nitrogen dioxide and/or 0.5% of water vapor in addition to the iodine
of any concentration, and it has been established that the presence of these substances
does not adversely affect the absorption efficiency of iodine species. The process
of the present invention therefore permits direct introduction of the gas containing
iodine into the gas-liquid contact equipment without pretreatment which, as well as
the simplicity of the post-processing equipment, allows extremely simplified design.
According to the process of the present invention, iodine which precipitates as insoluble
iodide can readily be separated by any usual method. Only this sediment needs to be
removed as radioactive waste according to the system of the present invention and
the quantity of radioactive waste is therefore much less than when using conventional
dry or wet methods, this being one of the important advantages of the present invention.
Detailed Description of the Invention
[0015] The following Examples describe in detail the system in accordance with the present
invention, but are not to be construed as limiting.
Example 1.
[0016] A dry air containing 200 ppm of iodine was allowed to pass at a rate of 0.5 l/min
through 50 ml of a silver nitrate solution of 10 mol/l concentration at a constant
temperature of 20°C. The iodine concentration at the outlet changed with time as shown
in FIG. 1. The percentage of the iodine removed from the gas stream, at the time when
the total volume of gas passed was 26 l, was 99.885%. This value may be converted
to the decontamination factor of DF=6.7 × 10³ (DF=Iodine concentration at the inlet/Iodine
concentration at the outlet). The concentration of residual silver ion in the solution
after breakthrough was 0.005 ppm or less. This means that more than 99.9977% of the
silver initially present in the solution was effectively utilized.
Example 2.
[0017] Simulated DOG gas, containing 200 ppm of iodine, 2000 ppm of nitrogen dioxide, and
5000 ppm of water, was allowed to pass at a rate of 0.5 l/min through silver nitrate
solutions of 10, 50 and 100m mol/l. The iodine concentrations in the gas measured
at the outlet showed time variations as shown in FIG. 2. This figure shows that the
total amount of iodine absorbed is nearly proportional to the concentration of silver
nitrate. The percentage of silver utilized effectively was 99.9977% or greater in
every case. Comparison between Example 1 and the experiment of 10m mol/l in Example
2 indicates that the presence of NOx in the gas produces no appreciable effect on
the absorption of iodine.
Example 3.
[0018] An experiment was carried our under the same experimental conditions as in Example
2 using a solution containing 4 mol/l nitric acid and 50 mmol/l silver nitrate. The
iodine concentration in the treated gas changed with time as shown in FIG. 3 and a
comparison with the case of 50m mol/l in Experiment 2 indicates that the absorption
of iodine is hardly affected by the nitric acid in the solution. This result also
suggests that the effect of nitric acid, which may be produced as a result of the
absorption of nitrogen dioxide in water as shown by the 3NO₂ + H₂O = 2HNO₃ + NO, would
be small.
Example 4.
[0019] An experiment was carried out using a silver sulfate solution with a concentration
of 12.5m mol/l under the same experimental conditions as in Example 2. The iodine
concentration in the gas at the outlet changed with time as shown in FIG. 4. This
shows that the silver sulfate solution is able to remove iodine as effectively as
a silver nitrate solution. The concentration of residual silver ion after breakthrough
was below 0.05 ppm. This is equivalent to a percentage of silver utilization of 99.998%
or greater.
[0020] In conclusion, from the foregoing, it is apparent that the present invention provides
a novel method for the removal of iodine and iodine compounds from mixture gases or
vapors using a solution containing silver ions, having the foregoing enumerated characteristics
and advantages.
[0021] It is to be understood that the invention is not to be limited to the exact details
of operation, or to the exact compounds, composition, methods, procedures, or embodiments
shown and described, as modifications and equivalents will be apparent to one skilled
in the art, and the invention is therefore to be limited only by the full scope which
can be legally accorded to the appended claims.